IR 05000245/1980022
| ML19345F136 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/15/1980 |
| From: | Sanders W, Lester Tripp, Walton G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19345F133 | List: |
| References | |
| 50-245-80-22, NUDOCS 8102060792 | |
| Download: ML19345F136 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT g
Regica I Report No.
50-245/80-22 Docket No.
50-245 License No.
OPR-21 Priority Category C
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Licensee:
Northeast Nuclear Eneroy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Nuclear Energy Station, Unit 1 Inspection at:
Waterford, Connecticut Inspection conducted: October 29-31 and November 5-7 and 12-14,1980 Inspectors: M,8,44/i.
/2-09-To G. A. Walto'1, Reactor nspector date signed-W/ W >./ des
/ 2 ~ 4 f ' 80 W. F. Sanders, Reactor Inspector date signed Approved by: M $. d,,dn
/245"/89
'L. E. Tripp, Chief. Engineering date signed Support Section, RC&ES Branch Inspection Summary:
Inspection on October 29-31 and November 5-7 and 12-14,1980 (Recort Number 50-245/80-22)
Areas Inspected: Boutine inspection of the inservice inspection program and associated _
inspections beinS conducted during the refueling outage.
In addition, inspections were made of the torus modifications, core spray sparger inspection results, feedwater sparger replacement, core spray line replacement, CRD line modification, main steam line restraints inspection results, and isolation condenser line examinations. The inspection involved 70' inspector-hours onsite by two regional based inspectoss.
Results:
No items of noncompliance or deviations were identified.
Region I Form 12 (Rev. April 77)
8102060 D 1
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t DETAILS 1.
Persons Contacted Northeast Utilities Service Company
- R. Herbert, Superintendent, Unit 1
- E. Mroczka, Station Services Superintendent T. Mawsca, Project Engineer-Core Spray
- K. Thomae., Plant Test Engineer T. Starr, Engineer J. Leason, ISI Coordinator, Unit 1 D. Korsec, Engineer K. Gray, QA Supervisor M. Bigiorelli, Project, Torus Modification Newport News Industrial Corporation M. Warren, QA Manager S. Carmean, QA/QC Supervisor General Electric
E. Reczek, ISI Project Manager D. Holthaus, ISI-Level III C. N. Flagg Company S. Senico, Quality Control Engineer Chicago Bridge and Iron Company S. VanWingerden, Quality Control Engineer NDT Enoineering - Hartford Steam Boiler L. Johnson, Quality Control Inspector
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2.
Torus Related Modification This inspection was made to examine the activities related to the modification the Mark I torus, in accordance with the long range program and ASME,1977
' tion with Addenda through Summer 1978 of the Boiler and Pressure Vessel de.
The following list of items summarize the modification:
Vent Header Downcomers Shortened 2' 3-3/8" in length per drawing
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_ B5266-0 to reduce the depth of immersion Installation of tubular cross supports 2-1/2" schedule 40 pipe between
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header downcomers per drawing A 4808, Revision 4.
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Addition of plant stiffeners to the sides of the torus spray header
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supports Additkon of braces to the bottom of (3) T quencher supports, con-
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sisting of 8" schedule 80 pipe installed in an angular position between the torus ring girder and midway of the support Addition of one 10" vacuum breaker in the safety relief valve line
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per C5270, Revision 0
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Installation of new 18" vacuum breaker disc
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Installation of 28 thermowells through wall of torus per B5264-0
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Modification of the cat walks with the addition of pipe supports
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Installation of /ent header deflectors and supports
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Addition of support saddles underneath torus shell
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Reroute of LPSI piping and extension of piping from top of torus to
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bottom of torus inside The following procedures were reviewed:
C.N.F.-Q-11, Procedure for Dry Magnetic Particle Examination
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C.N.F.-B-111, Revision A, Nondestructive Examinations
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WP1-34-I-34, SMAW PIGRI/PIGRI Weld Procedure Specifications
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WP1-34-I-34, SMAU PIGRI/PIGRI Weld Procedure Qualification Record
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WP1-34-III, SMAW Section XI Base Metal Repairs, Weld Procedure
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Specification WP1-34-III, SMAW Section XI Base Fktal Repairs, Weld Procedure
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Qualification Record C. N. F. -5004-13, Installation of Downcomers Modifications
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C. N. F.- 5004-17, Revision A, Base Metal Repair Requirements of ASME Section
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XI as Modified by TES/NUSCo Specification 05-2138-3 C. N. F. -5004-12, Revision A, Installation of Vent Header Deflectors and
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i Supports
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C.N.F.-5004-1, Installation of T Quencher
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C.N.F.-5004-5, Installation of Torus Thermowells
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C.N.F.-5004-14, Electrode Issuance Procedure
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Visual inspections were made of the work activities in progress on the outside of.the torus shell. Specific inspections were made of the fit-ups of saddles.at location no. 6 and 7 and the conditions of the butter and temper beads at location no. 8.
Observations were made of the ::agnetic particle examination in progress on no.11 butter.and temper bead and general observations made of the work conditions, presence of QC personnel, control
of weld material and general quality related activities.
Visual inspections were also made of the work activities in progress inside the torus.
The inspector noted that the inside of the torus shell had been cleaned with water laser equipment to reduce the level of radiation and to remove loose coating material.
Areas of base metal were recovered with new coating material. Observations were made of the vent header downconer cut-off'
and tie bar supports, reinforceant of spray header supports, additional cat walk supports and vent header deflector supports.
No items of noncompliance were identified.
3.
Core Spray Soarger Inspection The insper. car examined the results obtained by the licensee's contractor of the core spray spargers, using underwater camera and video recording equipment.
The inspection by the licensee was made for compliance with IE Bulletin 80-13.
No cracks were found and the spargers were found ac-ceptable.
No items of noncompliance were identified.
4.
Feedwater Sparcer Replacement The inspector reviewed the below listed documents ' applicable to the -in-stallation of new feedwater spargers and.aachining of. the feedwater nozzle cladding:
GE Procedure NNECo 2.0, Revision 0, dated 8/13/80,_ Tool and Eoutp-
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ment Control.
PORC approval 10/14/80 GE Procedure NNECo 3.0, Revision 0, dated 8/13/80, Cleaning end
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s Cleanliness Instructions GE Procedure NNEco 6.0, Revision 0, da.ted 8/14/80, Feedwater Sparger -
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Removal and Inspection i
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GE Procedure NNECo 14.0, Revision 0, dated 8/15/80, Post ibchining
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Nozzle-Nondestructive Testing GE Procedure NNECo 15.0, Revision 0, dated 8/15/80, Fit-up and In-
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stallation of the Feedwater Sparger GE Procedure NNECo 16.0, Revision 0, dated 8/15/80, Feedwater Sparger
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Welding Requirements GE General Welding Procedure SRSE 1-7, Revision 6, dated 9/3/80
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GE Detail Weld Procedure DWP-3004, Revision 6, dated 8/15/80
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GE ISE-WQ-23, Revision 7, dated 3/17/80, Welder Qualification Speci-
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fication GE Procedure 18XA9808, Revision 1, dated 9/3/80, NDE Procedure Visual
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Examinations Standard Traveler For Work Control
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No items of noncompliance were identified.
5.
Core Spray Line Replacement and Control Rod Drive Line Modification During the current outage the licensee is changing the core spray line in-side containment and removing and capping the control rod drive line. The inspector reviewed the below listed documents associated with these modi-fications.
The work is being performed by Newport News Industrial Corpora-tion in accordance with the ASME B&PV. Code Section III, 1977 Edition and Summer 1978 Addenda.
Welding Procedure 1633-K-W001, Revision C, dated 10/21/80
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Welder Qualification 1633-K-W002, Revision C, dated 10/24/80
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Weld Procedure Qualification P.Q. 00098
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Controlled Work Instructions
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Nondestructive Test Engineering, Liquid Penetrant Procedure 4100,
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Revision 2, dated 4/1/80 Material Test Report, QC Number 80NN1069, Heat N5415, ER 308 L Electrode
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Material Test Report-Piping P.O. 703517 Type 304, (.02 Max. Carbon).
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6.
Main Steam Line Restraints and Isolation Condenser Line Examination a.
Inspection by the licensee of the main steam line restraints revealed 2 restraints were cracked.
The cracks were found on restraints in steam line "A" and "D" loop, at the location of a 1/4" fillet weld connecting a plate to a structural conponent.
The cracks occurred in the center of the 1/4" weld, The licensee subsequently examined all restraints on the main steam lines and no additional cracks were found. No immediate cause for the failure has been determined, however, the licensee suspects the cracks occurred at the same time water hammer occurred in the isolation condenser supply lines.
The steam lines will be analyzed by the licensee in accordance with the requirements of IE Bulletin 79-14.
The licensee's corrective actions, in addition to that described above, is to liquid penetrant the attachment weld to pipe and reweld the support to structural steel per the original drawing.
The licensee has also performed volumetric examinations of 6 pressure boundary welds in main steam loop "A" and 7 pressure boundary welds in loop "D".
No defective welds were found.
The inspector had no additional questions at tnis time and no items of noncompliance were identified.
b.
As part of an augmented inservice inspection program, the licensee performed liquid penetrant examination on the inside surface of the supply line of the isolation condenser.
This requirement was re-quired because these welds are encapsulated in a guard pipe and could not be volumetrically examined from the outside.
The examination revealed cracks, later projected to be approximately 1/2" deep, and traversed circumferential1y 360 degrees in the heat affected zone of the weld. The licensee then expanded the scope of the examination to include the following:
Remove the guard pipe on both supply lines and perform ultrasonic
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examination on the welds Ultrasonically examine all welds in the supply and return line
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of the isolation condenser.
This included the class 1 lines in-side the primary containment Supplement the ultrasonic examination with radiography and liquid
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penetrant test on selective areas Evaluate the results of the data using procedures developed to
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detect intergranular stress corrosion cracks
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The licensee had completed ultrasonic exanination of the class 2 lines and found 9 welds which required further evaluation to-determine their disposition.
Six of the class 1 welds were com-pleted and 6 contained reflectors which required further evaluation.
The licensee's plans for those which will require repair have not been determined at this time.
The licensee has stated that NUREG 313, Revision 1 will be used to effect repairs.
No items of noncompliance were identified.
7.
Inservice Inspection Program The inservice examinations being performed during this outage represent a completion of the first ten year' inspection interval.
The examinations are being conducted in accordance with Section XI,1974 Edition including the Summer 1975 Adaenda, except for those exemptions granted in the provi-sions of 10 CFR F,0.55(a).
The inspector reviewed the below listed items applicable to the inservice inspection activity.
GE Procedure 160A7901, Revision 0, titled " Ultrasonic Examination
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of Pipe Welds for Intergranular Stress Corrosion Cracking" Personnel Qualifications of 3 Level II and.1 Level III in the examina-
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tion disciplines being performed i
Data review of bventy-five welds examined.
This included weld BHCB-1
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which is a circumferential weld in the reactor pressure vessel. This weld at location 350 degrees azimuth, gave ultrasonic signal amplitudes greater than 100 percent of the reference level.
The licensee had performed additional evaluation in accordance with the provi-ions of Section XI, Table IWB 3511.1.
It was established that the flaw was acceptable as a subsurface indication in accordance with Table IW3 3511-1.
Within the scope of this inspection, no items of noncompliance were identified.
8.
Jet Pump Beam Examination The inspector reviewed the results of ultrasonic examinations of jet pump.
beams which are provided to attach the ramshead to the jet pump assembly inside the reactor pressure vessel.
The examinations were performed to comply with IE Bulletin 80-07, BWR Jet Pump Assembly Failure.
The results indicate 5 beans are cracked and will be. replaced. Six beams are acceptable and 9 beams were reported as having signal responses which were conflicting.
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i The inspector reviewed the ultrasonic test data of the 9 beans which gave conflicting data.
This included discussions with the ultrasonic test examiner.
It was the insoector 's position that the nine questionable beams gave similar responses to those rejected. The inspector i
stated that if the 5 rejected beans are found to contain cracks when they L
are removed, then additional beams (worst case) should be removed and
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The licensee agreed to pull two additional beams if the'_five are found cracked.
This is an unresolved item pending further review by the licensee. (80-221
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Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-pliance, or deviations. An unresolved item disclosed during the inspection is discussed in Item 8.
10. Exit Interview I
The inspector met with licensee representatives (asterisked in paragraph 1)
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at the conclusion of the inspection on November 14, 1980.
The inspector summarized the purpose, scope and findings of the inspection as discussed herein. The licensee represenatives acknowledged the inspector's summariza-tion.
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